原子能科学技术Issue(12)：2238-2243,6.DOI:10.7538/yzk.2013.47.12.2238
SCWR-FQT 回路的冷却剂流量丧失事故研究
Loss of Coolant Flow Accident Analysis for SCWR-FQT Loop
周翀 1杨燕华1
作者信息
- 1. 上海交通大学核科学与工程学院，上海 200240
- 折叠
摘要
Abstract
The supercritical water-cooled reactor fuel qualification test (SCWR-FQT ) intends to test a small scale fuel assembly under supercritical water environment in a research reactor .For the safety system design and safety analysis of the test loop ,the modified ATHLET code was applied to model the loop ,and simulate two design basis accidents ,which caused partial or total loss of coolant flowin the fuel assembly test section .The calculated accidents were coolant bypassing the test section due to cracks in the internal structures of the pressure tube ,and primary pump seizure .T he calculation results showthat ,in the first accident the fuel cladding temperature shows a peak value of about 920 ℃ in the early stage of the transient ,while in the second accident the fuel cladding temperature suffers no obvious increase .It is suggested by the results that the current safety system design is able to provide effective cooling to the test section in the two simulated accidents .关键词
超临界水冷堆/ATHLET/冷却剂流量丧失事故Key words
SCWR/ATHLET/loss of coolant flow accident分类
能源科技引用本文复制引用
周翀,杨燕华..SCWR-FQT 回路的冷却剂流量丧失事故研究[J].原子能科学技术,2013,(12):2238-2243,6.
